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Event Notification Report for March 26, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/23/2001 - 03/26/2001

                              ** EVENT NUMBERS **

37682  37684  37779  37799  37809  37844  37861  37862  37863  37864  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37682       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/24/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 07:36[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/23/2001|
+------------------------------------------------+EVENT TIME:        07:25[EST]|
| NRC NOTIFIED BY:  ABRAMSKI                     |LAST UPDATE DATE:  03/23/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |STEVEN DENNIS        R1      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE.                  |
|                                                                              |
| The flow controller for the High Pressure Coolant Injection (HPCI) system is |
| indicating approximately 1400 gpm with the HPCI system in the standby        |
| condition.  Because the cause of this condition is not known at this time,   |
| the HPCI system is considered inoperable.                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * RETRACTED AT 1528 EST ON 3/23/01 BY MARK ABRAMSKI TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| "Engineering evaluation subsequent to this event has determined that the     |
| HPCI system would have performed its' intended function as credited in the   |
| LOCA analysis and therefore this 10 CFR 50.72 notification is retracted."    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Kenneth         |
| Jenison) has been notified.                                                  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37684       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/25/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 06:53[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/25/2001|
+------------------------------------------------+EVENT TIME:        02:47[EST]|
| NRC NOTIFIED BY:  M ADRAMSKI                   |LAST UPDATE DATE:  03/23/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEVEN DENNIS        R1      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.                  |
|                                                                              |
| At 0247 ET on 01/25/01, the flow transmitter controller for HPCI system      |
| spiked from zero to approximately 1500 gpm.  The HPCI system was in standby  |
| lineup at the time.  The flow indication has been slowly drifting down.      |
|                                                                              |
| A similar event occurred on 01/23/01 at 0725ET.  HPCI was declared           |
| inoperable.  The flow transmitter, 23FT-82, and flow switch, 23FS-78, were   |
| vented and a small amount of air was noted.  The flow indication returned to |
| zero (normal standby indication).  After a HPCI operability surveillance     |
| test, HPCI was declared operable at 1332 ET on 01/24/01.                     |
|                                                                              |
| After the second flow indication perturbation on 01/25/01, HPCI was again    |
| declared inoperable with an LCO start date of 01/23/01 at 0725 ET (7 days to |
| returned HPCI to operable status).  The cause of this condition is still     |
| under investigation.  All other systems are operable.                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * RETRACTED AT 1528 EST ON 3/23/01 BY MARK ABRAMSKI TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| "Engineering evaluation subsequent to this event has determined that the     |
| HPCI system would have performed its' intended function as credited in the   |
| LOCA analysis and therefore this 10 CFR 50.72 notification is retracted."    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Kenneth         |
| Jenison) has been notified.                                                  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37779       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 02/24/2001|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 03:24[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        02/24/2001|
+------------------------------------------------+EVENT TIME:        03:06[EST]|
| NRC NOTIFIED BY:  RAY MARTIN                   |LAST UPDATE DATE:  03/25/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFEGUARDS DEGRADATION RELATED TO AREA BOUNDARY                              |
|                                                                              |
| IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY                          |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.   ADDITIONAL DETAILS MAY   |
| BE OBTAINED FROM THE OPERATIONS CENTER.                                      |
|                                                                              |
| * * * RETRACTED AT 2121 EST ON 3/25/01 BY RAY MARTIN TO FANGIE JONES * * *   |
|                                                                              |
| The licensee is retracting this event based on reportability evaluation.     |
| Additional details may be obtained from the operations center.               |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.  The R1DO         |
| (Kenneth Jenison) was informed.                                              |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37799       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 03/02/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 10:10[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/02/2001|
+------------------------------------------------+EVENT TIME:        05:30[EST]|
| NRC NOTIFIED BY:  KENNEDY                      |LAST UPDATE DATE:  03/23/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT DECLARED RCIC INOPERABLE.                                              |
|                                                                              |
| During a panel walkdown, it was discovered that the RCIC flow controller     |
| setpoint pointer was indicating erratically.  Therefore, the flow controller |
| was declared inoperable resulting in RCIC being declared inoperable.         |
| Troubleshooting is currently being performed on the controller.  This        |
| condition put the plant in a 14-day LCO action statement.                    |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| * * * UPDATE 1055EST ON 3/23/2001 FROM ERIC OLSON TO S. SANDIN * * *         |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "During a control room tour on Friday, March 2, 2001, the output of the      |
| reactor core isolation cooling system (RCIC) controller FIC-1340-1 was       |
| observed oscillating between downscale (-value) up to approximately +2% as   |
| indicated on the output demand meter. Initial testing measured voltages at   |
| the input test terminals and found a steady flow signal applied to the       |
| controller. Voltage measurements taken at the output test jacks found the    |
| output oscillating between 9 to 11 milliamps, consistent with the            |
| oscillation of 2% on the demand meter. In an effort to help pinpoint the     |
| source of this problem, the set-point tape was adjusted down to the minimum  |
| value allowing the deviation meter to come on scale ( 10% measuring the     |
| signal error between flow input and set-point). In this mode, oscillation of |
| the deviation meter was observed, consistent with demand. The controller was |
| then taken to manual and the output demand meter became stable.  These two   |
| simple functional checks suggested the source of oscillation was limited to  |
| the automatic control circuitry of the GEMAC controller, based on the stable |
| voltage measurement at the controllers input and the stable output when      |
| placed in manual. The most probable cause for the oscillation would be       |
| weak/aging power supply capacitors used in the controller's automatic        |
| circuitry.                                                                   |
|                                                                              |
| "The RCIC system was declared inoperable and the NRC was notified at 1010 on |
| March 2, 2001 in accordance with 10CFR50.72(b)(3)(v) based on the belief     |
| that the controller was not operable.                                        |
|                                                                              |
| "Troubleshooting was performed and it was decided to replace the controller  |
| with the identical controller from the RCIC alternate shutdown panel (ASP).  |
| RCIC was then tested using procedure 8.5.5.1 with satisfactory results. The  |
| controller that had been removed from the RCIC panel was bench tested and    |
| the results indicated that the controller would have allowed the RCIC system |
| to reach a stable rated 400 gpm flow control.                                |
|                                                                              |
| "On Friday March 9, 2001, the controller from the alternate shutdown panel   |
| was also noted to be oscillating about the '0' position, repeating the       |
| condition described in PR01.9190. Problem report PR01.9210 was written to    |
| describe this similar condition. It was concluded that the RCIC test could   |
| be performed with the controller exhibiting some oscillation. The test       |
| results demonstrated that the controller and therefore, RCIC was operable.   |
| Further troubleshooting is in progress to determine the cause of the         |
| oscillations. One possibility is that the source of the oscillations has to  |
| do with equipment grounding and other equipment tests occurring on Fridays.  |
| Further investigation is in progress.                                        |
|                                                                              |
| "The reporting criteria of 10 CFR 50.73 were evaluated as follows;           |
|                                                                              |
| "For (a)(2)(v); not reportable. The initial observation on Friday, March 2,  |
| 2000, of oscillations on FIC-1340-1 indicated that the individual controller |
| was inoperable and needed maintenance. The controller was replaced with the  |
| identical controller from the alternate shutdown panel (ASP). The newly      |
| installed controller was tested and RCIC was verified to be operable. Bench  |
| testing of the removed controller indicated that it would have performed its |
| safety function. A similar oscillation was noted on the new controller on    |
| Friday March 9, 2001. RCIC was tested even though the controller appeared to |
| be oscillating. The testing verified the operability of the installed        |
| controller and confirmed the conclusion that the original controller would   |
| have been operable. Since the original controller would have been operable,  |
| the observed oscillations could not have prevented the fulfillment of the    |
| RCIC safety function and therefore, is not a reportable condition.           |
|                                                                              |
| "It is recommended that the 10 CFR 50.72 notification made on March 2, 2001  |
| be retracted."                                                               |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R1DO(Jenison).   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37809       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 03/05/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 17:56[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        16:00[EST]|
| NRC NOTIFIED BY:  K BELDEN                     |LAST UPDATE DATE:  03/23/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM EMERGENCY VENTILATION DECLARED INOPERABLE.                      |
|                                                                              |
| Control Room Emergency Ventilation was declared inoperable at 1600 hours.    |
| This was a result of the Lab carbon sample analysis not meeting Technical    |
| Specification 3.4.5.c of  greater than 90%  radioactive methyl iodine        |
| removal capability when tested.   This required entering into a 7 day        |
| shutdown Limiting Condition for Operation.  Carbon sample analysis is        |
| required per Technical Specification to be performed once per cycle (2       |
| years).  Licensee is in the process of replacing the carbon.                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event.                       |
|                                                                              |
| * * * RETRACTED AT 1411 EST ON 3/23/01 BY JOHN PARRISH TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| After further testing and calculations it was determined that the value was  |
| above the technical specification requirements and the event was not         |
| reportable and retracts the event notification.                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.  The R1DO         |
| (Kenneth Jenison) has been informed.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37844       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/17/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 10:55[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/16/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/23/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |GEOFFREY WRIGHT      R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SPAETH                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN - GEOMETRY VIOLATION                                  |
|                                                                              |
| At 1100 on 3/16/01, a seal test buggy was found without signs or tags as     |
| required by NCSA-PLANT_031 (Potable Sampling/Test Buggies and Carts).  Upon  |
| investigation of the test buggy, the chemical trap was found to have a       |
| nominal diameter of four inches and a length of twenty two inches.  The four |
| inch diameter violates the passive design control 2(b) which requires a      |
| three inch nominal diameter and a thirty three inch length.  Nuclear         |
| Criticality personnel have determined the maximum loading of the effected    |
| trap to be 76 gram U-235 at 3% assay.  76 grams is lower than the 350 gram   |
| safe mass limit.  The NCSE contingency analysis considers credible, a        |
| maximum five inch nominal diameter to remain subcritical.                    |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| Safety significance is considered very low. The NCSA requirement is three,   |
| three inch nominal diameter chemical traps.  However, the NCSE allows for    |
| three, five inch nominal diameter chemical traps and remain subcritical,     |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW            |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| Based on the bounding calculations for five inch diameter chemical traps,    |
| there no critical pathways involved                                          |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
|                                                                              |
| Geometry is the controlled parameter that was violated                       |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| The amount of uranium is unknown, however, it is not expected to be above    |
| 350 grams U-235 due to the operation performed with this buggy and the fact  |
| that the maximum loading of a 4" X 22" chemical trap is only 76 grams U-235  |
| at 3% assay.                                                                 |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| The control violated was the geometry control of the chemical trap.  The     |
| chemical trap was required to be three inch schedule 40 pipe, but it was     |
| found to be a nominal four inch diameter pipe.                               |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED;   |
|                                                                              |
| The test buggy was posted with temporary signs as required by                |
| NCSA-PLANT_031.  The buggy will remain in the anomalous condition boundary   |
| until NDA results are obtained.  Disposition of the buggy will be determined |
| based on the NDA results.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.  The DOE Representative will be     |
| informed.                                                                    |
|                                                                              |
| * * * UPDATE AT 1346 EST ON 3/23/01 BY JIM McCLEARY TO FANGIE JONES * * *    |
|                                                                              |
| "NDA measurements show the chemical trap described above contains 1.6 +/-    |
| 0.8 grams and the pump contains 1 gram of U-235. Total U-235 content         |
| including error is 3.4 grams U-235. TSR 3.11.2 requires an NSCE for          |
| operations with uranium enriched to 1 wt% and contains 15 grams or higher    |
| U-235. Therefore this buggy is not a fissile material operation and not a    |
| violation of NCSA-PLANT_031."                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector and the DOE representative. |
| The R3DO (Gary Shear) and NMSS EO (Brian Smith) were notified.               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37861       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 03/23/2001|
|LICENSEE:  TWINING LABS                         |NOTIFICATION TIME: 19:02[EST]|
|    CITY:  FRESNO                   REGION:  4  |EVENT DATE:        03/16/2001|
|  COUNTY:                            STATE:  CA |EVENT TIME:        07:00[PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/23/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGGER               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN MOISTURE DENSITY GAUGE                                                |
|                                                                              |
| The Twining Labs reported a stolen Troxler moisture density gauge, Model     |
| 3430, serial # 20467.  The sources are nominal 30 millicuries of Cs-137 and  |
| 10 millicuries Am-241/Be.  The local police were notified (police report #   |
| 01-23615) and a reward was posted for the return.  The theft occurred on     |
| 3/16/01 about 0700 PST.                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37862       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 03/24/2001|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 08:35[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        03/24/2001|
+------------------------------------------------+EVENT TIME:        03:08[PST]|
| NRC NOTIFIED BY:  C. PERINO                    |LAST UPDATE DATE:  03/24/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |
|                                                                              |
| "This report is being made in accordance with 10 CFR 50.72(b)(2)(i).         |
|                                                                              |
| "Columbia Generating Station started a plant shutdown 03:08. At 23:15        |
| yesterday, a rise in drywell pressure was observed Coolant leakage was       |
| confirmed by a rising trend in drywell particulate monitors. Upon            |
| investigation, this leakage was confirmed to be due to cycling RCIC-V-63,    |
| the RCIC steam supply inboard isolation valve, during the performance of a   |
| Surveillance Procedure.                                                      |
|                                                                              |
| "At 23:30, a rise in drywell unidentified leakage rate was observed. At      |
| 01:56 an entry into Technical Specification 3.4.5.B for greater than a 2 gpm |
| rise in a 24 hour period was made. At 03:08, an entry into Technical         |
| Specification 3.4.5 A was made for unidentified leakage greater than 5 gpm.  |
| At this time, the decision to begin a controlled reactor shutdown was made.  |
|                                                                              |
| "RCIC-V-63 was backseated to terminate leakage at 03:55. At 03:58 it was     |
| determined the backseating successfully stopped the leakage. The downpower   |
| was terminated at 04:19. Indications of leakage are trending down. At 04:30, |
| the leakage had decreased below the Technical Specification limits and       |
| reactor power was increased to 100%."                                        |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37863       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 03/24/2001|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 10:39[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/24/2001|
+------------------------------------------------+EVENT TIME:        00:30[CST]|
| NRC NOTIFIED BY:  STEVEN SEWELL                |LAST UPDATE DATE:  03/24/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       88       Power Operation  |88       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING DISCHARGE OF WATER OFFSITE                    |
|                                                                              |
| "On 3/24/01, at 0845, a determination was made that a report to the TNRCC    |
| [Texas Natural Resource Conservation Commission] is required for a discharge |
| of water to Squaw Creek Reservoir. An estimated 1000 gallons of fire         |
| protection water was discharged due to a ruptured pipe in warehouse C. The   |
| water contains no hazardous constituents that have assigned reportable       |
| quantities; however, a report to the TNRCC will be made in accordance with   |
| water quality regulations."                                                  |
|                                                                              |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37864       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 03/24/2001|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 19:24[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        03/24/2001|
+------------------------------------------------+EVENT TIME:        16:01[CST]|
| NRC NOTIFIED BY:  FRED VANBUSKIRK              |LAST UPDATE DATE:  03/24/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRESSURE BOUNDARY DEGRADATION FOUND DURING TESTING AFTER SHUTDOWN            |
|                                                                              |
| "On March 18, 2001, following shutdown for a scheduled refueling outage,     |
| Arkansas Nuclear One (ANO) Unit I performed a routine visual inspection of   |
| the Reactor Vessel (RV) head area per NRC Generic Letter 88-05. This         |
| inspection revealed an increase in the amount of boric acid crystals in the  |
| area of one Control Rod Drive Mechanism (CRDM) nozzle over the amount that   |
| had been present during the previous inspection. Results of the visual       |
| inspection were inconclusive regarding the source of the leakage. No other   |
| CRDM nozzle showed similar boron buildup. Prior to unit shutdown, on March   |
| 16 the total unidentified Reactor Coolant System leak rate was determined to |
| be 0.087 gpm, significantly less than the 1 gpm allowed by Technical         |
| Specifications. After the RV head was removed and placed on the storage      |
| stand, additional inspections were conducted. At approximately 1601 on March |
| 24, 2001, eddy current and ultrasonic testing revealed an RCS pressure       |
| boundary leak. Using ultrasonic test (UT) methods one crack was identified   |
| in the wall of CRDM nozzle #56. The UT data indicates that the crack is on   |
| the downhill side of the nozzle. It extends approximately 0.8 inches below   |
| the weld and extends upward to approximately 1.0 inches above the weld. The  |
| depth of the crack is approximately 0.2 inches. This crack is consistent     |
| with industry experience associated with Primary Water Stress Corrosion      |
| Cracking (PWSCC) in similar components that have been evaluated as part of   |
| the NRC Genetic Letter 97-01 response. These cracks do not pose a            |
| significant safety risk during plant operation. ANO plans to perform repairs |
| during the current outage.  Since the crack resulted in leakage through the  |
| Reactor Coolant System pressure boundary, this condition is being reported   |
| as a non-emergency eight-hour report in accordance with 10 CFR               |
| 50.72(b)(3)(ii), degradation of a principal safety barrier."                 |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+